Fabrication and calibration of new carbon-14 reference standards using irradiated graphite from uranium–graphite reactors

Abstract

The paper deals with measurements of carbon-14 in irradiated nuclear graphite. It suggests approaches to the problem, impart experience in production and calibration of new C-14, reference standards got from irradiated elements (sleeve, block) of the uranium–graphite reactor (UGR) stacks. Reference standards in the form of irradiated graphite were created and certified by the C-14 concentration. The concentration of C-14 in different samples was determined by interlaboratory comparisons. Results of the work proved an opportunity of creating reference materials for the C-14 radionuclide based on irradiated graphite obtained from the graphite elements of the uranium–graphite reactors. C-14 reference standards with different concentrations of interfering Cl-36, Co-60, H-3, Cs-137, Sr-90 and other radionuclides can be used for future development of new methods of determination the C-14 concentration in irradiated graphite and spectrometric equipment calibration.